ML20132D289
| ML20132D289 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/16/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20132D294 | List: |
| References | |
| NUDOCS 8507310277 | |
| Download: ML20132D289 (26) | |
Text
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UNITED STATES
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, [,
p, NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 y
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated January 23, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8507310277 850716 DR ADOCK 05000368 p
e.
2.
Accordingly, Facility Operating License No. NPF-6 is hereby amended by adding paragraph 2.C.(7) to read as follows:
(7) IAEA Safeguards 1.
INCORPORATION OF FACILITY ATTACHMENT:
The licensee shall implement Codes 2 through 7 of Facility Attachment No. 8 dated June 1, 1985, to the US/IAEA Safeguards Agreement.
2.
INTERPRETATION OF FACILITY ATTACHMENT:
For purposes of this license amendment, the Facility Attachment shall be interpreted in accordance with the following:
Facility Attachment Code 2.2 The types of modifications with respect to which information is required, under 10 CFR 75.11, to be submitted in advance are those items stated in Code 2.2.
"Any change in the rated thermal output for continuous operations" means:
Any change that exceeds the rated thermal output for continuous operation as described in Paragraph 14 of the Design Information Questionnaire (DIQ) dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
"Any change in the access routes to the reactor area" means:
Any new entrances / exits involving SNM fuel routes or any deletion or modification of existing entrances / exits involving SNM fuel routes or new openin shown in Paragraph 10 (Attachment 10.7)gs other than and Paragraph 56 (Attachment 56.2) of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
"Any change in the design of the reactor fuel" means:
Any change in the design of the reactor fuel that would exceed the maximum quantity in weight and specifications stated in Paragraphs 24 (Attachment 24.1),25,26(Attach-ment 26.1) and 27 (Attachments 27.1 and 27.2) of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.ll(c).
- "Any change in the type of fuel used, e.g., introduction of mixed oxide fuel" means:
Any changes involving the use of fresh fissile material other than U-235.
"Any change in the method of identifying individual fuel assemblies" means:
-Identification method other than the use of fuel assembly serial numbers.
"Any change of the refueling equipment or methods" means:
Any introduction of new, additional or modified major equipment which would cause a significant deviation from the fuel handling process and description as specified in Paragraph 13 of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
"Any change in connection with the reactor vessel or its cover influencing access to the core" means:
Any change that would facilitate the introduction or removal of fuel in a manner that circumvents or significantly changes current practices.
" Introduction of new loop heat removal equipment which will be required to increase the nominal rated core thermal power level" means:
Any introduction / installation of new, modified or addi-tional loop heat removal equipment which would permit increases in the core thermal output from Paragraph 14 of the DIQ dated August 22, 1983, or as modified in accordance with 10 CFR 75.11(c).
" Installation of any fuel assembly dismantling, decladding j
or dissolution equipment" means:
The introduction (installation) of equipment necessary to extract special nuclear material from the fuel rods.
"Any change in the health and safety regulations affecting the conduct of inspection by the Agency" means:
i Any change in the Licensee's health and safety procedures which would preclude Agency access to areas containing special nuclear material and/or any alteration to the procedures described in Paragraph 54 of the DIQ dated August 22, 1983.
"Any change in the methods of storage for irradiated fuel and of the spent fuel storage capacity" means:
Any change in the information in Paragraph 48 of the DIQ dated August 22, 1983, which addresses spent fuel storage plans, method of storage, design capacity of storage and/or spent fuel shipment.
"Any change in other parts of the DIQ to be submitted when the change has been completed" means:
Any modification in the other parts of the design information provided in the DIQ will be submitted when the first inventory change report (ICR) is submitted after the modification (s) has been completed according to 10 CFR 75.11(c)(2).
Facility Attachment Code 6.1.1 "The requirement for reporting of Inventory Change Reports (ICR's) (when calculated)" shall mean:
When calculated every six months per the recording requirements specified in Code 5.1.1.
Facility Attachment Code 6.2
" Concise Notes" means those reports that are required to be submitted pursuant to 10 CFR 75.34 and 75.35 on DOE /NRC Form 740M and prepared in accordance with printed instruc-tions for completing the form.
Facility Attachment Code 7
" Inspection" means:
Inspection or inspections as described in 10 CFR 75.42 and as conducted by duly authorized representatives (inspectors) of the International Atomic Energy Agency (IAEA).
t-Facility Attachment Code 7.3 Code 7.3 shall not be interpreted as requiring a minimum actual inspection effort or any other obligation on the part of the licensee to assure that any such minimum actual inspection effort is applied.
"30 man-days per year if one refueling occurs" shall be interpreted to mean:
The anticipated IAEA inspection effort under ordinary circumstances.
=..
Facility Attachment Codes 7.4.2 and 7.4.3
" Verification of the inventory, i.e., by item counting and identification" means:
The IAEA inspection effort may include the verification of all, or any portion of, the licensee's SNM inventory (fuel assemblies in the core are subject to verification only during refueling and not at any other time).
The IAEA's inventory verification procedures may include confimation of the stated location and serial numbers of fuel assemblies using procedures that are practical and that are within both the IAEA's and the licensee's technical capabilities.
Facility Attachment Code 7.10 The specific facility health and safety rules and regulations to be observed by the Agency's (IAEA) inspectors, as specified in Paragraph 54 of the design information as of August 22, 1983, provided by the USA means:
Agency inspectors who have previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special sTtuation that has occurred at the facility since the inspectors' last visit to the facility. The briefing will be of a short duration, not to exceed 30 minutes, covering topics deemed relevant by the licensee.
Agency inspectors who have not previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special liiftuation that has occurred at the facility. The briefing will be of an appropriate duration, not to exceed three hours, and consist of topics deemed relevant by the licensee.
In either case, the licensee should take into account the Agency inspector's prior training, expertise and experience.
In neither case shall the Agency inspector be subject to any form of evaluation or testing by facility representatives or representatives of the U.S. Government.
For health and safety reasons, Agency inspectors will be escorted by qualified facility personnel at times deemed appropriate by the licensee.
l e
3.
USE OF EQUIPMENT:
The Agency (IAEA) is normally permitted to routinely use portable equipment for their independent material verifications. However, notwithstanding incorporation of Facility Attachment Code 7.5 in this license, the installation of fixed equipment pursuant to said Code 7.5 is not required except in accordance with such additional conditions as may subsequently be added to this license.
4.
TERMINATION:
Pursuant to the provisions of 10 CFR 75.41, the Comission will inform the licensee, in writing, when its installation is no longer subject to Article 39(b) of the principal text of the US/IAEA Safeguards Agreement. The IAEA Safeguards License Conditions incorporating Code 7 of the Facility Attachment as part of NRC License No. NPF-6 will be terminated as of t.Se date of such notice from the Comission. However, since the IAEA may elect to maintain the licensee's installation under Article 2(a) of the Protocol, provisions equivalent to Codes 2 through 6 of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeguards License Conditions to NRC License No. NPF-6 will remain in effect until the Comission notifies the licensee otherwise.
If this option is not selected by the IAEA, the Comission will then notify the licensee that all License Conditions pertaining to the US/IAEA Safeguards Agreement are terminated.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 8:J,/. 818 Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing Date of Issuance: July 16, 1985 t
i';..
'd
.OO41W D#0017 Text, prepared on:
1985-01-04 Date of entry into force:
ggy g y gg Safeguards Agreement Under NPT between the USA and the IAEA Subsidiary Arrangements Facility Attachment No. 8 ARXANSAS NUCLEAR ONE-UNIT 2 (ANO-2),
Facility: UXKR
/
MBA: UXKR Total number of pages: 20 Page No. 1 Code General Agreement Part Reference Reference (Articles)
(Codes) 1.
43(a)
Identification of the facility Facility identification code:
UXXR.
1.1 Name, owner and operator Name:
Arkansas Nuclear One-Unit 2 (ANO-2)
Owner and operator: Arkansas Power and Light Company.
1.2 Geocraphic location Pope County, Arkansas, USA.
1.3 Postal address P.O. Box 608 Russelvillo, Arkansas, 72801 Telephone No. (501) 964 3100 1.4 Description s
The power station consists of one pressurized light water reector, 2015 MW(t) gross thormal power.
- Refuelling intervel: nor:aclly 12 - 18 months
- Number of assemblies discharged normally on refuelling:
50 - 75
- Nominal weight of fuel in assomblios:
476l19 t.ntal v wd um
- ta.aximum fresh fuel enrichment (U 235):
4.1%
- Number of fuel assemblies in core:
177
- Fresh fuel storage capacity:
63 e
.w en =
=
p
,s y..
'Tcat prepared on: 198!H)l-04 D ta of cntry into forca: JUN O 1 m
' Facility Attachment No,'S ARKANSAS NUCLEAR ONI-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 2 Code General Agreement Part Reference Reference (Articles)
(Codes) 1.4 (cont'd)
- Spent fuel storage capacity:
988
- Fuel rods may be exchanged between fuel assemblies at the time of refuelling.
1.5 Maps and plans See Design Information Questionnaire (DIQ).
2.
3.1 43, 44, Information on the facility 46(a)
This facility attachment is based on the design information as of 22 August 1983, provided by USA.
2.1 8
Location of information Identical sets of the information proviced en the facility are kept at the Agency, et the faci'ity and at the USNRC Headquarters.
2.2 3.1.3 45 Chances in the desien information on the facility to be provideo in advance 3.1.4 (With reference to the relevant paragraphs in the Design Information Questionnaire).
- Any change in the rated thormal output for continuous operation.
(14)
- Any change in the access routes to the reactor area.
(10)
- Any charr30 in the design of the reactor fuel.
(24, 25, 27)
"' *~~'-
- Any change in the type of fuel used 0 9 Introduction of nired orton fuel.
(22, 23 16)
- Any increase in inc maximum cr.richment-c.f the fuel.
(23)
- Any change in the method cf identifying individual fuel as somblies.
(31)
~
Tcat pr; pared cn:
1905-01-04 D:ts of cntry into fcres: JUN g y g Faci}jty Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 3 Code General Agreement Part Reference Reference
( Articles)
(Codes) 2.2 (cont'd)
- Any change in the refuelling equipment or methods.
(41)
- Any change in connection with the reactor vessel or its cover influencing access to the core.
(43)
- Introduction of new irradiation cositions inside the reactor vessel.
(44)
- Introduction of,you Igop heat removel equi pment' which... oe required to increase the nominal rated core th.ermal power level.
(52)
- Installation of any fuel decladding or dissolution equipment.
(51)
- Any change in the routes of the shipoing cask for irradiated fuel within the
~
facility.
(50) 3.2.2
- Any change in the health and safety regulations affecting the conduct of inspection by the Agency.
(54)
- Any change in the methods of storage of irradiated fuel and of the spent fuel storage capacity.
(4G)
Any change in other parts of the design information to be submitted when the thcnge has been cumpleted.
3.
Safriuards measures 3.1 29 Accountanc/
3 1
26(b)
Material balanco aroas anc their identif:catsu.- cece:
The ANO-2 nuclear facility UXKR cunstitutes one material balance area UXFR.
2 emo o e
e e
^
TE,xt prepared on:
198 5-01-04 Data cf entry ints forco: Jg g g
,Fccility Att chment No. 8 F.RKANSAS NUCLEr.R OL'E-UNIT 2 ( ANO-2)
Facility: UXKR / MBA: UXKR Page No. 4 Code General Agreement Part Reference Reference (Articles)
(Codes) 3.1.2 46(b)
Strategic ocints which are Key Measurement 37, 38 Points (KMPs).
(For their specifications see Code 4. )
(a) For determination of nuclear raterial flow:
6.3 KMP 1 - Roceipts, accidental gains and de-cuemptions of nucloer materiel.
.KMP 2 - Nuclear loss and production 3.5, 3.7 KMP 3 - Shipments of nuclear material, 6.3,.7.1 withdrawals, exemptions and accidental losses.
(b) For determination of the physical inventory:
KMP A - Frcsh fuel storage and inspection area.
KMP D - Reactor core.
KMP C - Spent fuel storage racks and spent
~
fuel shipping cesks.
KMP D - Other locations of nuclear material at the facility.
3.1.3 46(c)
Physical inventory takino (PIT)
Nominal timing:
4 As soon as possible after the compirtion of each refuelling and beforo the reactor is closed again.
In caso of prolonged shutdrwn of one year or l ur.g o r. physacal in.cr. tory tak:nejs,nal! co pe r f o rto.' ( s t ry 1.' msr.*.h' Fuol other than thet contained in the core will be inventoried at least once por year.
.e
Tcxt prepared cn:
1985-01--04 Dat:2 cf cntry into forco: JW 6 2 g Fccility Ctt:chment No. 8 CRKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 5 Code General Agreement Part Reference Reference (Articles)
(Codes) 3.2.1 (cont'd)
Procedures:
Item counting and identification. Preparation of an itemized inventory list for each inventory KMP.
3.2 29 Containment and Surveillance 3.2.1 46(f),
Strateoie points for the application of containment and surveillanco measurns
- Reactor h'all.
- The fresh and spent fuel storage areas including access routes.
3.2.2 73(d),(e)
Installed Aoencv instruments and devices (a) Seals to ensure the containmcnt of the reactor vessel.
(b) Cameras for survoillance of fuel movements into or out of the reactor containment including the fresh and spent fuel storage areas.
(c) Seals on shipping casks with spent fuel.
(d) Seals on Agency equipment.
If there is a need to break a seul cr inLorfere with the operation of safeguards instruments, the Agency shall be informed in advance by the fastout moans.
The :n forn.a t '. ;n shall include the (probabic) date on which the nperation will take place. If a seal is
' ~ ~ * - -
removed in the absence of an Agency inspecto-without the operator being able to 2nform tno Agency in advante, u special report will be pr o:porud u n spusified in Code C.4.;
3.3 6.1 31, 35 specific provisions and c*itoria for termination of safeguaj s on nuclear material None.
L l.
,Tcat prepared (n:
1985-01-04 Data of cntry into forca: JUN 0 J 19g3 Facility Attachment No. O ARKANSAS NUCLEAR ONE-UNIT 2 ( ANO-2)
Facility: UXKR / M8A: UXKR Page No. 6 Code General Agreement Part Reference Reference (Articles)
(Coces) 3.4 6.2 36, 37 Specific provisions and criteria for exemptinq nuclear material from safeguards None.
3.5 3.7, 7.1 12(a)
Specifi provisions and criteria for withdet wal of nuclear mate-ial f rom saf oquards None.
i l
e
~
ide 4 preement Reference (Articles):
16(b), 55, 90 22' eecifications for Key Measurement Points 0 0.
C;C ede 4.1: KMPs for the flow of nutlear material E4 i
3 l
l Description of a typical l
l Material l Meas.l c3
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i l
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_l
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l Q/50H] N l l
l less than 0.01 effective l priate l concentration of uranium and.
l l
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g l Gain l
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I
ode 4.1: LMPs fer the iInw of nuclear material (centinued)
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l l
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l Material l Meas.]
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l Source data l Description l basts l m,i
_._. 1 Change ___l hatch l__1 tem l
_l_NRC_l IAEA l l
EN f
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l l
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KMP 1 above; l
l l
l
- 7.
- 4 l Nuclear loss l One fuel assembly.
l assem-l (3) Estimated burn _up of each fuel l
l BQ1G l M l 3
5 l (burn.up) l l
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l l
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l One fuel assembly.
l assem_ l (Pu-241 decay) for each fuel l
l l
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assembly when calculated, in_
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l BQ2F l N l
l~i l
l l
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l
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D 4.):
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l Q/50Hl M l T,
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l l
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4.2: KMPs fcr Physical Inventory cf nrclear materici Description of a typical l
l Material l Meas.l l
hatch l
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_ _ __ l ttem l l NRC l IAEA l l
((
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l l
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l l
l l
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l BQ1F l N l c l!
2 l
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l l
for untrradiated fuel; l
l BQ4F l N l
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l l
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calculated to allow for nuclear loss l
l l
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l l
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l Fer fuel assembites l One l (1) Identification number; l
l BQ1G l M l l
l fuel l (2) Weights of total and fissile urantum l l BQ2G l M l l Un2 fuel assembly.
l assem. l and total plutonium as calculated to l
l l
l l
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allow for nuclear loss and production l l
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l For small quantitics of nuclear maler tall Not l (1) Weight of compound; l
l Q/SOAl N l o
E E
l (eaci ~les's than 0.01 clicctive kilogr_amll applic. l (2) Weights of total and fissile uranium. l l Q/50lll N,M l P Q l
l able l
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9 l Any number of such quantitles.
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Tcat prepared cn:
1985-01-04 Dato cf cntry into forco: J(lN O I 1985 Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2')
FaciFity: UXKR / MBA: UXKR Page No. 11 Code General Ag reement Part Reference Reference (Articles)
(Codes) 5.
46(d), 49 Records System 5.1 2.1.2 54, 32(f)
Specific provisions for accountino records 5.1.1 54(a),
Inventory changes (for the soecifications of source data see Code 4.1 above), time of re co rding
- Receipt (KMP 1):
Upon r4ceipt.
- Nuclear loss (uranium burn-up) and nuclear production (KMP 2):
When calculated, includin's upon discharge.
- Nuclear loss (Pu-241 decay) (KMP 2):
When calculated, including upon shipment.
- Shipment (KMP 3):
Upon shipment.
6.2
- Exemption (KMP 3):
Upon the accounting transfer of the nuclear material.
6.3
- De-exemptions (KMP 1):
Upon the accounting transfer of the nuclear material.
s 3.5
- Accidental loss (KMP 3):
Upon determining the amourit of the loss.
- Accidental gain (KMP 1):
Upon determinirn the amour t of the goin.
3./, 7.1
- Withdrawal (KMP 3):
Upon withdrawal.
W
, Tcxt preparcd en:
1985-01-04 Dat3 of Ntry into forco: Jg g y Fac'ility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 12 Code General Agreement Part Reference Reference
( Articles)
(Codes) 5.1.2 4.2 54(b),
Measurement (item counting and identification) results used for determination of the physical inventory (for the specifications of source data see Code 4.2 above) and time of recording
- For all physical inventory KMRs:
Upon identification and counting of items during the physical inventory taking.
- Itemized list of nuclear nateriel inventory:
Before inventory verification.
5.1.3 54(c)
Adiustments and corrections, time of recordino
- Shipper /Receivor difference:
Not relevant.i MUF:
Normally identical to zero.
Corrections:
Whenever errors have been found.
5.2 2.1.2 56 specific provisions for operatinq records 5.2.1 55(a)
Operating data used to establish changes in the quantities and composition of nuclear material
- Location of each fuel assembly at any time.
e
- The rolovant source data with respect. to nuclear loss and production, including-(6) The
..c ;thly integrat:d ther.tal po.cr procuced by the reactor; and (b) The es tinated burn-up (in FWO/t) for er.ch fuel assembly
- Deto end duration of any reactor shutdown.
- Date and description of any dismantling operation of a fuel assembly for pin c a c ha ng e.
l l
l
Tcxt prepared cn:
1985-01-04 Data of cntry into f,creo:
JUN 0 2 365 FacilJty Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 13 Code General Agreement Part Reference Reference
( Articles)
(Codes) l 5.2.2 56(b)
Calibrations Not required.
5.2.3 56(c)
Secuence of the actions taken in preparino for and in takine the physical inventory
- At physical inventory KMPs:
Dates'end description of the actions taken and the results obtained.
An itemiz'ed list of nuclear material inventory after completion of inventory taking by the operator but before commencement of verificction by the Agency.
5.2.4 56(d)
Actions taken in order to ascertain the cause and maonitude of any accidental or unmeasured loss Dates and description of the actions taken and the results obtained.
5.3 50 Location and lanaua'oe of records At the facility and et the utility headquarters in Little Rock (Arkansas):
- English, s
5.4 51 Rotention period for records l
Fivo years.
l l
6.
10 46(d), 57 Poports system l
6.1 3.4.1 61(a), 62 Specific provisions for inventory chance 63 reports (ICRs}
l 6.1.1 10 Contents The inventory changes to Lt-reported a*e those typos specified in Codo 5.1.1 abovo.
Will be completed as specified in sections 1 through 4 of Code 10, General Part of the Subsidiary Arrangements.
I 1
x Text preparcd kn: 1985-01-04 Da'th of cntry into terca:
JUN o f g85 Facility Attachment No. 8 ARMANSAS NUCLEAR ONE-UNIT 2 (ANO-1)
Facility: UXKR / M8A: UXKR Page 103. 14
\\
Code General Agreement Part Reference Reference (Articles)
(Coc'e s )
6.1.1 (cont'd)
Nuclear loss and production for irradiated; fuel assemblies will be reported when c&lculated, including as of the date of discharge. The elecent code of the initial fuel category will be used in reporting.
5.1.2 Timing or frequency of dispatch Within 30 days after the end of the month in which receipt, discharge, shipment, exemption, i de-exemption, withdrawal or accidental loss or gain occurred or oas established.
y,
s 6.2 3.4.1 62 Specific p ovisions for' concise notes
\\
- 6. 2.1 -
62(a)
Concise notes explaining the inventory chanoes
- May be attached to ICRs (or mailed-
.srncrately) containing the data on nuclear
\\
Icss and production, to state the burn-up in MWD /t of initial uranium for each fuel batch
,]
calculated.
^
- May be attached to ICRs (or mailed separately) to explain unusual inventury.:
changes (such as accidental loss) or correction. They may also be used to s,-
explain any other part of information Nincluded in the reports.
Concise notes describing the anticipated 6.2.2 62(b) 31 operational programme; subject and timino of r
dispatch
- Planned operations involsir.g removal of the Agency reactor sossol scal, e.g. refuelling, fresh fuel receipts, and spent fuel
\\.
shipments.
s To be Ltta:hed to oc:S.Mi:R ( s c r O.'.d 4 07.
below) erid to cavsr the peric,d until the e d of the next refuelling.
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.. s Text prcpared on:
1985-01-04 Dato cf cntry into forco:
JW 0 2 g Faci,1,ity Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 15 Code General Agreement Part Reference Reference (Articles)
(Codes) 6.2.2 (cont'd)
- Forecast for the next refuelling, physical inventory taking or spent fuel shipment, including information about the shipment casks to be used ard the extent to which these are expected to be filled.
To reach the Agency at least 30 days in advance, subsequent changes thoroto as soon as they are known.
6.3 3.4.2 61(b), 65 Specific provisions for material balanco reports (MBRs) 6.3.1 10 Contents
- The consolidated inventory changes to be reported are those types specified in Code 5.1.1 above.
- Will be completed as specified in sections 1 through 4 of Code 10, General Part of the Subsidiary Arrangements.
6.3.2 10 Physical inventory listinos (Pits) to be attached to MBRs The batch data included in PILs will be based on the shipper's data on the initial nuclear material content of the fuel for unieradiated fuel assemblics in KMPs A and 8 and for small quantities and on operator's data for irradiated fuel assemblics in KMPs B and C.
Will be completed as specified in sections I through 4 of Code 10, General Part of the Subsidiary Arrangements.
6.3.3 Timino or frequoney of disoatch Within 30 days of the physical inventor, tak ing under Code 3.1. 3 above.
Tcat prepared on:
1985-01-04 Data of cntry into fccco:
M 02 g Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (AMO-2)
Facility: UXKR / M84: UXKR Page No. 16 Code General Agreement Part Reference Reference (Articles)
(Codes) 6.4 3.5 66, 89(b)
Special reports 6.4.1 Specification of circumstances requiring submission of special reports (a) Loss limits:
One fuol assembly.
(b) Changes in containment:
Physical integrity of a fuel assembly as an accounting unit is accidentally broken;
- Any Agency containment and surveillance device, referr.ed to in Code 3.2.2 such as a seal or camera, is interfered with or removed in the absence of Agency inspectors, unless the Agency has been informed in advance as provided for.
1/
6.4.2 3.5 66, 89(b)
Contents, as appropriate
- Date when the incident or circumstance occurred.
- Description of the actions taken in order to ascertain the cause of the incident or circumstance and the magnitude of the loss.
- Cause and features of the incident or circumstance.
Estimated amount of nuclear material which l
has been lost.
i
. 7.
c 2 * * * ~~
Inspections
, - 7.1 70, 02 tyde of routino inspections Intermittent.
1/ In respect of seals on shipping casks. this requircnont applies only while the casks remain in the facility.
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Tcat pecpared en:
1985-01-04 Dato of cntry into ferco:
g y
Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / M8A: UXMR Page No. 17 Code General Agreement Part Reference Reference (Articles)
(Codes)
.7. 2 78 Applicable formula and procedure for determination of maximum routine inspection effort Article 7B(a) of the Agreement.
7.3 76, 79 Indication of the actual routine inspection ef fort under ordinarv circumstances Indication of the ectual routino inspection ef fort, as,far as can be foreseen and assuming-3.1 (a) Circumstances at the facility to be as described in the design information provided; 2.0 (b) The continued validity of the information on the national system of accounting for and control of nuclear material, as set out in the General Part of the Subsidiary Arrangements ;
(c) That the refuelling period is as stated in para. 37 of the Design Infornation.
20 man-days per year.
7.4 72, 73 Indication of the seboo of routine inspections under ordinary circumstances
7.4.1 General
Examination of records, verificatien for nolf-consisteney end consistency with repurts.
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F
,Tc:;t prepared on: 1985-41-04 Dato of cntry into fcrco:
JUN g y Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
Facility: UXKR / MBA: UXKR Page No. 18 Code General Agreement Part Reference Reference (Articles)
(Codes) 7.4.2 At inventory KMPs Verification of the inventory, e.g. by item counting, identification and integrity checks and non-destructive measurements.
7.4.3 At flow KMPs Verification of inventory changes, e.g. by itom counting. identificatiun and integrity checks and non-destructive measurements of fresh and irradiated fuel, including the use of seals on containers of irradiated fuel.
7.4.4 At strategic points for containment and surve i llanc e
- Observation of refuelling and spent fuel removal operetions;
- Application, examination and removal of Agency seals used in accordanco with Code 3.2.2, as well as of other seals:
- Servicing and maintenance of the surveillance equipment.
7.5 73(d)
Arrangements for the use by the Aqoney of equipment for indooendent measurements Specific arrangements for the use of Agericy equipment to be made as the need arises.
7,6 9.4 73(a)
Duplicates ard additional sarelos for the poency Not rolovant.
I.7 8 's. 86 Persons tn whom a request for any oceration o r, for services
.t the fneilit,y should bn addressed Vice President for Nuclear Operations Tolcphone No.-
(501) 371 7901
n-1
- e.
)
s r.
Text prepared on:
198!H)1-C4 Date of entry into force:
MUN O I 1985 Facility Attachment No. 8 ARKANSAS NUCLEAR ONE-UNIT 2 (AMO-2)
Facility: UXKR / MSA: UXKR Page No. 19 Code General Agreement Part Reference Reference (Articles)
(Codes) 7.8 Contacts at the facility General Manager, ANO Telephone No.: (501) 964 3100 7.9 14, 86 Services and charaos 7.9.1 Services provided by the operator with no charge to the Agency
- Health and safety services (protective clothing, dosimeters).
- Office space for the Agency's inspectors.
- Power supply for the Agency's instruments.
- Personnel for handling the fuel assemblies during their measurements.
~
- Available equipment for handling the fuel assemblies during their measurements.
- Personnel to escort and facilitate audit activities.
7.9.'2 Services provided by the operator with charges to the Acency
\\
- Means of communication (telephone, telex, cabic):
According to cxisting rates.
If any specific request by the Agene;y for services riot covered above gives rise to expenses for which reimbursement is requested from the Agency, the Agency shall be notified of the estimated expenses bofore the service is performed. The Agency will only reimburse such expensos if it has ennfirmed its init..sl request and agreed in writing to the amount involved.
v 7
.a Tcxt prepared on: 1985-01-04 0;to of cntry ints fccco:
'IUN 01 1985
. Facility Attachment No. 8 f,RNANSAS NUCLEAR ONE-UNIT 2 (ANO-2)
- Facility: UXKR / M8.1: UXXR Page No. 20 Codo General Agreement Part Reference Reference (Articles)
(Codes) 7.9.3 Mode of reimbursement of the expenses charged to tha Agency By cheque, after receipt of the invoice by the Agency.
7.10 3.2 44 Specific facility health and safety rules and regulations to be observed by the Agencv's inspectors As specified in paragraph 54 of the design information as of 22 August 1983 provided by the USA.
The Agency inspcetors will be informed at the facility by short briefings at the time of entry into the,,fac'l tv of g h-
- health and safeTV u os o a57noc rules as might be required in view of a special situation that has occurred at the facility.
For health and safety reasons, inspectors will be escorted by qualified personnel.
8.
4.1.3 30, 88 Agency statements 8.1 88(a)
A summary statement will be made on the result of each inspection within 30 days of its completion.
8.2 08(b)
A statomont on the conclusions the Agency has drawn from its verification activitics in respect of the facility will be mado within 60 l
days after the end of the month in which the Agency has verified the physical inventory.
l The statement will include, as apcropriate, cunclusions drawn frum:
(a) Records examination; (b) Reports to the Agoney; (c) Verification of containment and surveillance mwasurus; i
l (d) Verification of inventory changes; (c) Verification of matorial accountancy; (f) Verification of the quality and functioning of the uporator's measurement system; (g) Activitics in respect of MUF, shipper /'
recei ver d i f ference s and/or Intset L